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{{#Wiki_filter:'acility Name: Peach Bottom Date of Extam: 12/08/2008 SRO-Onlv Points A2 I G* I Total *,- *I lote 1. 2. 3. 4. 5. 6. 7.* a. 9. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (Le., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each WA category shall not be less than two). The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate! by +I from that specified in the table based on NRC revisions.
{{#Wiki_filter:'acility Name: Peach Bottom                                 Date of Extam:12/08/2008 SRO-Onlv Points A2       I     G*     I   Total
The fiial RO exam must total 75 points and the SRO-only exam must total 25 points. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added.
                                                                                                          -,*
Refer to Section D.l .b of ES-401 for guidance regarding the elimination of inappropriate WA statements. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before select,n$
lote   1.
I*
Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (Le., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each WA category shall not be less than two).
: 2.      The point total for each group and tier in the proposed outline must match that specified in the table.
The final point total for each group and tier may deviate! by +I from that specified in the table based on NRC revisions. The fiial RO exam must total 75 points and the SRO-only exam must total 25 points.
: 3.      Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to Section D.l .b of ES-401 for guidance regarding the elimination of inappropriate WA statements.
: 4.      Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before select,n$
a second topic for any system or evolution.
a second topic for any system or evolution.
Absent a plant-specific priority, only those WAS having an importance rating (IR) of 2.5 or higher shall be selected.
: 5.      Absent a plant-specific priority, only those WAS having an importance rating (IR) of 2.5 or higher shall be selected.
Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories.
: 6.      Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories.
The generic (G) WAS in Tiers I and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.l .b of ES-401 for the applicable WAS. On the following pages, enter the WA numbers, a brief description of each topic, the topics' importance ratings (IRs) for the applicable license level, and the point totals
7.*      The generic (G) WAS in Tiers Iand 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.l .b of ES-401 for the applicable WAS.
(#) lor each system and category. Enter the group and tier totals for each category in the table above; if fuel handling eqiuipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #I does not apply). Use duplicate pages for RO and SRO-only exams.
: a.      On the following pages, enter the WA numbers, a brief description of each topic, the topics' importance ratings (IRs) for the applicable license level, and the point totals (#) lor each system and category. Enter the group and tier totals for each category in the table above; if fuel handling eqiuipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note # I does not apply). Use duplicate pages for RO and SRO-only exams.
For Tier 3, select topics from Section 2 of the WA catalog, and enter the WA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3.
: 9.      For Tier 3, select topics from Section 2 of the WA catalog, and enter the WA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to WAS that are linked to 10 CFR 55.43.
Limit SRO selections to WAS that are linked to 10 CFR 55.43. ES-401, Page 17 of 34 ES-401 2 Form ES-40'I-I - - ES-401 Form ES-41 1- I1 Em 1) EIAPE #I Name I Safety Function 295001 Partial or Complete Loss of Forced ll Core Flow Circulation I 1 & 4 295003 Partial or Complete Loss of AC I6 295004 Partial or Total Loss of DC Pwr I6 295005 Main Turbine Generator Trip I3 11295006 SCRAM I1 11295016 Control Room Abandonment I 7 295018 Partial or Total Loss of CCW I8 295019 Partial or Total Loss of Inst. Air I8 295021 Loss of Shutdown Cooling I4 295023 Refueling Acc I8 295024 High Drywell Pressure I5 295025 High Reactor Pressure I3 11 295027 High Containment Temperature I5 295028 High Drywell Temperature I5 I--- 295030 Low Suppression Pool Wtr Lvl I5 ~~ 295031 Reactor Low Water Level I2 I1 295037 SCRAM Condition Present Reactor Power Above APRM Downscale or 295038 High Off-site Release Rate I9 600000 Plant Fire On Site I 8 Disturbances I 6 ~ 11WA Category Totals: - BWR Examination Outline lency and Abnormal Plant Evolutions -Tier IIGroup 1 (RO) 
ES-401, Page 17 of 34
- ES-401 3 Form ES-404 -1 ~~ ~~ ES-401, Page 19 of 34 ES-401 4 Form ES-401-1 IlES-401 BWH Examination Outline Form ES-401-1 ES-401, Page 20 of 34 ES-401-1 5 Form ES-401-1 ES-401, Page 22 of 34
 
~~ ES-401 2 Form ES-401 - BWR Examination Outline Form ES-4C 1 - ES-401 95025 High Reactor Pressure  
ES-401                                                               2                                 Form ES-40I-I
/ 3 Containment conditionslisolations 295038 High Off-site Release Rate  
                                                                                                                        -
/ 9 00000 Plant Fire On Site / 8 or Voltage and Electr Form ES-40"11 - ES-401 3 ES-401, Page 19 of 34 ESQOI 4 Form ES-401-1 ES-401, Page 20 of 34 ES-401 5 Form ES-401-1 6 ES-401 BWR IExamination Outline Form ES-401-1 Plant Svsterns - Tier 2/GrOUD 2 (SRO) ES-401, Page 21 of 34 ES-401 Generic Knowledge and Abilities Outline (Tier
ES-401                                                     BWR Examination Outline                          Form ES-41 1-I1                                           Em lency and Abnormal Plant Evolutions -Tier IIGroup 1 (RO)
: 3) Form ES-401-3 1- Category 1. Conduct of Operations
: 1)        EIAPE # I Name I Safety Function l 295001 Partial or Complete Loss of Forced Core Flow Circulation I 1 & 4 295003 Partial or Complete Loss of AC I 6 295004 Partial or Total Loss of DC Pwr I 6 295005 Main Turbine Generator Trip I 3 11295006 SCRAM I 1 11295016 Control Room Abandonment I 7 295018 Partial or Total Loss of CCW I 8 295019 Partial or Total Loss of Inst. Air I8 295021 Loss of Shutdown Cooling I 4 295023 Refueling Acc I 8 295024 High Drywell Pressure I 5 1 295025 High Reactor Pressure I 3 295027 High Containment Temperature I 5 1I I---
: 2. Equipment Control 3. Radiation Control 4. Emergency Procedures I Plan Tier 3 Point ?:Peach Bottom Date of Exam:12/0~3/2008 RO I SRO-Only IR) # IIRI # KIA # Topic 2.1 . 01 IKnowledge of conduct of operations requirements 13.81 I I Knowledge of individual licensed operator responsibilities related to shift staffing, such as 10CFR55, etc 2.1 . 04 medical requirements. "no-solo" operation, mainte-lance of active license status 3.3 1 2.1 . 17 IAbiIity to make accurate, clear, and concise verbal reports 13.91 1 I I 4.6 1 2. . 45 4.3 1 Knowledge of procedures, guidelines.
295028 High Drywell Temperature I 5 295030 Low Suppression Pool Wtr Lvl I 5
or limitations associated with reactivity 2.1. 37 management Ability to identify and interpret diverse Sndications IQ validate the response of another indicator 2.1. Subtotal 2.2. 3.9 1 Ability to determine the expected plant configuration using design and configuration control documentation, such as drawings, line-ups tag-Outs.
      ~~
etc I 2.2. 2 1 (Knowledge of pre- and post-maintenance operabi1Ml.y requirements I 2.9 I I 3.8 1 2.2. I 2.2. Subtotal IKnowledae of radioloaical safetv orinciDles Dertaini L. 2.3. 12 containmh entry re&rements fuel handling responsibilities access lo locked high- 3.2 1 radiation areas. alianina filters.
295031 Reactor Low Water Level I 2 295037 SCRAM Condition Present Reactor Power Above APRM Downscale or 295038 High Off-site Release Rate I 9 600000 Plant Fire On Site I 8 Disturbances I 6
etc Knowledge of radiation or contarnination hazards that may arise during normal abnormal or emergency conditions or activities Knowledge of radiological safety procedures pertaining to licensed operator duties such reSDOnSibilitieS.
                      ~                   -
access to locked hiah-radiation areas. alianina filters.
11WA Category Totals:
etc Knowledge of radiation or contamination hazards thal may arise during normal abnormal or emergency conditions or activities 34 1 2'3. 2.3. 1 3 as response to radiation monitor alarms containment entry requirements, fuel handling 3.8 1 38 1
 
* 3. I 2.3. I 2.3. Subtotal Knowledge of the bases for prioritizing safety functi 2.4. 22 operations I 4.2 I 1 I Knowledge of RO tasks performed outside the mairi control room during an emergency  
ES-401           3
'2.4. 341 and the resultant ODerational effects 4.1 1 4.5 1 2.4. 45 IAbility to prioritize and interpret the significance of f?ach annunciator or alarm II I 4.3 I 1 I 2.4. I Subtotal rota1 ES-401, Page 27 of 34 ES-401 Record of Rejected WAS Form ES-401-4 Tier / Group Q#46 RO1/1 Q#48 ROIII Q#52 RO1/1 Q#57 RO1/1 Q#65 RO1/2 Q#5 RO2/1 Q#8 RO2/1 Q#l7 RO2/1 Q#23 RO2/1 Q#33 RO212 Q#37 RO2/2 Q#79 SRO2/1 Q#85 SRO 1 / 1 Randomly Selected Reason for Rejection WA 295019 At Peach Bottom, there is no impact on RHRlLPCl from loss of instrument AK2.19 air other than the inabiliity to manually stroke testable check valves. (Replaced with 295019 AK2.05) 295023 Unable to construct an'RO question for this WA that meets the 2.2.42 requirements of NUREG-1021. (Replaced with 295023 2.4.31) 295028 Application of Technical Specifications is not an RO job function. 2.4.40 (Replaced with 295028 2.2.22) 600000 Unable to construct an RO question for this WA that meets the AK1.01 requirements of NUREG-1021. (Replaced with 600000 AKI .02) 295036 Unable to construct an RO question for this WA that meets the EK2.02 requirements of NUREG-1021. (Replaced with 295036 EK2.01) 209001 Unable to construct an'RO question for this WA that meets the K3.03 requirements of NUREG-1021. (Replaced with 209001 K3.02)
                                        -
Unable to construct an RO question for this WA that meets the K1.04 requirements of NUREG-1021. (Replaced with 21 5003 K1.02) Unable to construct an RO question for this WA that meets the K6.09 requirements of NUREG-1021. (Replaced with 261000 K6.03) 263000 Unable to construct an RO question for this WA that meets the 2.4.18 requirements of NUREG-1021. (Replaced with 263000 2.1.23) 226001 At Peach Bottom, there are no automatic operations associated with the A3.02 Containment Spray mode of RHR/LPCI based on "system pressure". (Replaced with 226001 A3.01) 245000 Unable to construct an RO question for this WA that meets the 2.2.39 requirements of NUREG-1021. (Replaced with 245000 2.1.20) 261 000 There are no conditions and limitations in the facility license associated 2.2.38 with the Standby Gas Treatment System. (Replaced with 261000 2.2.40) 295016 Unable to construct an SRO question for this WA that meets the A42.07 requirements of NUREG-1021. (Replaced with 295016 AA2.06) 215003 261000 ES-401, Page 27 of 33 
Form ES-404 -1
, ES-301 Administrative ToDics Outline Form ES-301-1 Facility: Peach Bottom Examination Level: RO SRO 0 Date of Examination: 12/08/2008 Operating Test Number: 2008 NRC Administrative Topic (See Note)
      ~~     ~~
Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Plan TY Pe Code-* N. S N, R D. S Describe activity to be performed G2.1.29 - Lineup Standby Gas Treatment System For Automiatic Operation (New - SO 9A. 1 .A COL) Not Required G2.2.41 - Isolate the 2A Turbine Building Closed Cooling Water IPump Due to a System Leak (New - P&ID M-316) G2.3.11 - Perform PRO Duties For A Liquid Radwaste Dischairge (2001 NRC) G2.4.3!3 - Activate The Emergency Response Data Systerrt (PLOR-186C)
ES-401, Page 19 of 34
NOTE: All items (5 total) are required for SROs.
 
RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.
ES-401               4             Form ES-401-1 IlES-401     BWH Examination Outline     Form ES-401-1 ES-401,Page 20 of 34
* Type Codes
 
& Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (5 3 for ROs; 5 4 for SROs & RO retakes) (N)ew or (M)odifiied from bank (2 1) (P)revious 2 exams (5 1; randomly selected)
ES-401-1               5       Form ES-401-1 ES-401, Page 22 of 34
ES 301, Page 22 of 27 
 
-_____ ES-301 Administrative Topics Outline Form ES-301-1 Facility: Peach Bottom Examination Level: RO SRO , Date of Examination: 12/08/2008 Operating Test Number: 2008 NRC Administrative Topic (See Note)
                                                                                                  ~~
Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Plan TY Pe Code* N. R D, R Describe activity to be performed G2.1.34 - Review And Evaluate Reactor Coolant System Chemistry Limits - Condenser Tube Leak at Power (New - CH-10, ON-126, TRM 3.9) ~ ~ G2.1.26 - Determine Minimum Required Personal Protective Equipment For Racking Out A 480 Volt Breaker (New - SA-AA-129)
ES-401                                       2                                     Form ES-401-1
G2.2.6 - Review And Approve A Temporary Procedure Change (PLOR-222C)
                                                                                                    -
G2.3.1:3 - Review And Approve Primary Containment PurgeNent Isolation Valve Cumulative Hour Log (2007 NRC) ~ G2.4.40 - Make EAL Classification And State/Local Notifications For ALERT - High Winds With Visible Plant Damage (PLOR-234C)
ES-401                                BWR Examination Outline                           Form ES-4C 1 -
95025 High Reactor Pressure / 3 Containment conditionslisolations 295038 High Off-site Release Rate / 9 00000 Plant Fire On Site / 8 or Voltage and Electr
 
ES-401          3                    -
Form ES-40"11 ES-401,Page 19 of 34
 
ESQOI               4       Form ES-401-1 ES-401, Page 20 of 34
 
ES-401                     5                 Form ES-401-1   6 ES-401       BWR IExamination Outline           Form ES-401-1 Plant Svsterns - Tier 2/GrOUD 2 (SRO)
ES-401,Page 21 of 34
 
ES-401                   Generic Knowledge and Abilities Outline (Tier 3)                                                     Form ES-401-3
-1             ?:Peach Bottom                  Date of Exam:12/0~3/2008 Category    KIA #                                                Topic RO   I SRO-Only I R ) #   I I R I #
2.1. 01 IKnowledgeof conduct of operations requirements Knowledge of individual licensed operator responsibilitiesrelated to shift staffing, such as 13.81      I      I 2.1. 04   medical requirements. "no-solo"operation, mainte-lance of active license status               3.3   1 10CFR55, etc 1.
2.1. 17 IAbiIity to make accurate, clear, and concise verbal reports                                   13.91   1 I     I Conduct of              Knowledge of procedures, guidelines. or limitationsassociated with reactivity 2.1. 37 management                                                                                                   4.6  1 Operations Ability to identify and interpret diverse Sndications IQ validate the response of another
: 2. . 45  indicator                                                                                                  4.3  1 2.1.
Subtotal Ability to determine the expected plant configurationusing design and configuration 2.2.      control documentation, such as drawings, line-ups tag-Outs. etc                               3.9    1 I
2.2. 2 1 (Knowledgeof pre- and post-maintenance operabi1Ml.y requirements I 2.9 I     I
: 2.                                                                                                                                3.8   1 Equipment Control 2.2. I 2.2.
Subtotal IKnowledaeof radioloaical safetv orinciDles Dertaini L     .
2.3. 12   containmh entry re&rements fuel handling responsibilities access lo locked high-             3.2   1 radiation areas. alianina filters. etc Knowledge of radiation or contarnination hazards that may arise during normal abnormal 2'3.      or emergency conditions or activities                                                         34    1 Knowledge of radiologicalsafety procedures pertaining to licensed operator duties such 2.3. 13  as response to radiation monitor alarms containment entry requirements, fuel handling                      3.8  1
: 3.                      reSDOnSibilitieS.access to locked hiah-radiationareas. alianina filters. etc Radiation Control
* 3.      Knowledge of radiation or contamination hazards thal may arise during normal abnormal or emergency conditions or activities I
38    1 2.3. I 2.3.
Subtotal Knowledge of the bases for prioritizing safety functi 2.4. 22  operations Knowledge of RO tasks performed outside the mairi control room during an emergency
              '2.4. 341and the resultant ODerational effects                                                         I 4.2 I  1   I
: 4.                                                                                                                    4.1    1 Emergency Procedures                                                                                                                        4.5   1 I Plan 2.4. 45 IAbility to prioritize and interpret the significanceof f?achannunciator or alarm I
I      I    I 4.3 I 1 2.4.
I Subtotal Tier 3 Point rota1 ES-401, Page 27 of 34
 
ES-401                   Record of Rejected WAS                                   Form ES-401-4 Randomly Tier /
Selected                                Reason for Rejection Group WA Q#46     295019  At Peach Bottom, there is no impact on RHRlLPCl from loss of instrument RO1/1     AK2.19  air other than the inabiliity to manually stroke testable check valves.
(Replaced with 295019 AK2.05)
Q#48    295023  Unable to construct anRO question for this WA that meets the ROIII      2.2.42 requirements of NUREG-1021.
(Replaced with 295023 2.4.31)
Q#52    295028  Application of Technical Specifications is not an RO job function.
RO1/1     2.4.40 (Replaced with 295028 2.2.22)
Q#57    600000  Unable to construct an RO question for this WA that meets the RO1/1     AK1.01  requirements of NUREG-1021.
(Replaced with 600000 AKI .02)
Q#65    295036  Unable to construct an RO question for this WA that meets the RO1/2    EK2.02  requirements of NUREG-1021.
(Replaced with 295036 EK2.01)
Q#5      209001  Unable to construct anRO question for this WA that meets the RO2/1      K3.03  requirements of NUREG-1021.
(Replaced with 209001 K3.02)
Q#8      215003  Unable to construct an RO question for this WA that meets the RO2/1      K1.04  requirements of NUREG-1021.
(Replaced with 215003 K1.02)
Q#l7    261000  Unable to construct an RO question for this WA that meets the RO2/1      K6.09  requirements of NUREG-1021.
(Replaced with 261000 K6.03)
Q#23    263000  Unable to construct an RO question for this WA that meets the RO2/1      2.4.18 requirements of NUREG-1021.
(Replaced with 263000 2.1.23)
Q#33    226001  At Peach Bottom, there are no automatic operations associated with the RO212      A3.02  Containment Spray mode of RHR/LPCI based on system pressure.
(Replaced with 226001 A3.01)
Q#37    245000  Unable to construct an RO question for this WA that meets the RO2/2      2.2.39 requirements of NUREG-1021.
(Replaced with 245000 2.1.20)
Q#79    261000  There are no conditions and limitations in the facility license associated SRO2/1      2.2.38 with the Standby Gas Treatment System.
(Replaced with 261000 2.2.40)
Q#85    295016  Unable to construct an SRO question for this WA that meets the SRO 1 / 1  A42.07  requirements of NUREG-1021.
(Replaced with 295016 AA2.06)
ES-401, Page 27 of 33
 
                                                                                                          ,
ES-301                            Administrative ToDics Outline                            Form ES-301-1 Facility: Peach Bottom                                                Date of Examination: 12/08/2008 Examination Level: RO         SRO  0                                Operating Test Number: 2008 NRC Administrative Topic            TYPe                      Describe activity to be performed (See Note)                Code-*
G2.1.29 - Lineup Standby Gas Treatment System For Conduct of Operations              N. S        Automiatic Operation (New - SO 9A. 1.A COL)
Conduct of Operations                                                Not Required G2.2.41 - Isolate the 2A Turbine Building Closed Cooling Equipment Control                  N, R        Water IPump Due to a System Leak (New - P&ID M-316)
G2.3.11 - Perform PRO Duties For A Liquid Radwaste Radiation Control Dischairge (2001 NRC)
G2.4.3!3 - Activate The Emergency Response Data Emergency Plan                    D. S Systerrt (PLOR-186C)
NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.
NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.
* Type Codes  
* Type Codes & Criteria:             (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (53 for ROs; 5 4 for SROs & RO retakes)
& Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (5 3 for ROs; 5 4 for SROs & RO retakes) (N)ew or (M)odified from bank (2 1) (P)revious 2 exaims (5 1; randomly selected)
(N)ew or (M)odifiied from bank (2 1)
ES 301, Page 22 of 27 ES-301 Control Room/ln-Plant Systems Outline Form ES-301-2 System / JPM Title Facility: Peach Bottom Exam Level: RO SRO-I 0 SRO-U 0 Type Code* Safety Function Date of Examination:
(P)revious 2 exams (5 1; randomly selected)
12/08/2008 Operating Test Number:
ES 301,Page 22 of 27
2008 NRC d. 209001 A4.04 - Core Spray System I Perform Pump Capacity Test For e. 223002 A4.03 - Primary Containment Isolation System
 
/ Perform a IST (Alternate Path - Minimum Flow Valve Fails To Open) - SET 3 Group I PClS Isolation Reset (GP-8A) (PLOR-024C) - SET 1 f. 262001 A4.04 - AC Distribution
                                            -_____
/ Excite The Main Generator (PLOR-031C) - SET 4 g. 212000 A4.14 - Reactor Protection System / Reset a Full Scram (PLOR-004C) - SET 2 h. 400000 A4.01 - Component Cooling Water I Verify Proper Isolation of Reactor Building Closed Cooling Water (RBCCW) (20135 NRC) - SET 3 A, L, M, S 4 D, EN, S 5 D, s 6 D, EN, L, S 7 D, p, s 8 a. 202001 A4.01 - Recirculation System
ES-301                             Administrative Topics Outline                           Form ES-301-1
/ Start a Recirc IPump (Alternate
                                                                                                          ,
: b. 295031 EA1.02 - High Pressure Coolant Injection
Facility: Peach Bottom                                               Date of Examination: 12/08/2008 Examination Level: RO         SRO                                   Operating Test Number: 2008 NRC Administrative Topic            TYPe                      Describe activity to be performed (See Note)              Code*
/ Manually Initiate Path - Scoop Tube Lockup) (PLOR-309CA) - SET ~. 4 HPCI (Alternate Path - Manual Initiation Pushbutton F,ails To Operate) c. 239001 A4.01 - Main Steam System / Open Main Steam Isolation Valves (2007 NRC / PLOR-300CA) - SET 1 After a Group-1 Isolation (PLOR-083C) - SET 2 i. 295037 G2.4.35 - Control Rod Drive Hydraulic Systerri / Isolate And Vent j. 217000 A2.04 - Reactor Core Isolation Cooling / Defeat Auto Open Signal k. 295028 EA1.03 - Drywell Chilled Water Low Level (Alternate Path - The Scram Air Header - Unit 3 (PLOR-074P) of RClC Torus Suction Valves - Unit 2 (NEW - A0 13.:3-2) Manual Makeup to Drywell Chilled Water System) - Unit 2 (NEW - ARC D, E, L, R 1 E, N, R 2 A, E, N, R 5 *Type Codes (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power I Shutdown (N)ew or (M)odified from bank including 1 (A) (P)revious 2 exams (WA I (S)imuiator Criteria for RO I SRO-I I SRO-U 4-6 I 4-6 I 2 <9 I58 I54 - >I I> 1/>1 - >I 111 121 - 22 I >2 I 21 < 3 I 5 3 I 5 2 (randomly selected)
Conduct of Operations                          G2.1.34 - Review And Evaluate Reactor Coolant System Chemistry Limits - Condenser Tube Leak at Power (New - CH-10, ON-126, TRM 3.9)
>I I >I 121 - I - I 2 1 (control room system) - - 1111 ES-301, Page 23 of 27 ES-301 Control Room/ln-Plant Iivstems Outline Form ES-301-2 a. 202001 A4.01 - Recirculation System
                                                                                              ~    ~
/ Start a Recirc IPump (Alternate
Conduct of Operations              N. R        G2.1.26 - Determine Minimum Required Personal Protective Equipment For Racking Out A 480 Volt Breaker (New - SA-AA-129)
: b. 295031 EA1.02 - High Pressure Coolant Injection
Equipment Control                  D, R        G2.2.6 - Review And Approve A Temporary Procedure Change (PLOR-222C)
/ Manually Initiate Path - Scoop Tube Lockup) (PLOR-309CA) - SET 4 HPCl (Alternate Path - Manual Initiation Pushbutton F,ails To Operate) (2007 NRC / PLOR-300CA) - SET 1 c. 239001 A4.01 - Main Steam System / Open Main Steam Isolation Valves d. 209001 A4.04 - Core Spray System
Radiation Control                              G2.3.1:3 - Review And Approve Primary Containment PurgeNent Isolation Valve Cumulative Hour Log (2007 NRC)
/ Perform Pump Capacity Test For e. 223002 A4.03 - Primary Containment Isolation Systern I Perform a ____. After a Group-I Isolation (PLOR-083C) - SET 2 IST (Alternate Path - Minimum Flow Valve Fails To Open) - SET 3 Group I PClS Isolation Reset (GP-8A) (PLOR-024C) - SET 1 f. ___ Facility: Peach Bottom Exam Level: RO 0 SRO-I Control Room Systems@ (8 for RO); (7 for SRO-I);
                                                    ~
(2 or :3 for SRO-U, including 1 ESF) Date of Examination:
Emergency Plan                                G2.4.40 - Make EAL Classification And State/Local Notifications For ALERT - High Winds With Visible Plant Damage (PLOR-234C)
12/08/2008 Operating Test Number: 2008 NRC SRO-U 0 ~ A, D, S 1 A, D, EN, 2 L, P, s D, L, S 3 A, L, M, S 4 D, EN, S 5 System / JPM Title I/ *Type Codes (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power I Shutdown (N)ew or (M)odified from bank including 1 (A) (P)revious 2 exams (WCA (S)imulator I Safety 1 I Function Criteria for RO I SRO-I I SRO-U 4-6 I 4-6 I 2 <9 158 I54 - >I I> 11 21 - >I 1>1121 - >2 I >2 I 21 - < 3 I 5 3 I 5 2 (randomly selected)  
NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.
>I I >I 121 - I - I 2 1 (control room system) - g. 212000 A4.14 - Reactor Protection System
* Type Codes & Criteria:              (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (53 for ROs; 5 4 for SROs & RO retakes)
/ Reset a Full Scram h. 400000 A4.01 - Component Cooling Water / Verify Proper Isolation of In-Plant Systems@ (3 for RO); (3 for SRO-I);
(N)ew or (M)odified from bank (2 1)
(3 or 2 for SIRO-U) D, EN, L, S (PLOR-004C) - SET 2 Reactor Building Closed Cooling Water (RBCCW)
(P)revious 2 exaims (5 1; randomly selected)
ES-301 Control Roomlln-Plant Svstems Outline Form ES-301-2 System / JPM Title Facility: Peach Bottom Exam Level: RO 0 SRO-I 0 SRO-U [XI Date of Examination: 12/08/2008 Operating Test Number: 2008 NRC Safety Type 'Ode* Function I/ d. 209001 A4.04 - Core Spray System / Perform Pump Capacity Test For Open) - SET 3 I Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) ! A, L, M, S 41 1; 1 1s f. g. 212000 A4.14 - Reactor Protection System I Reset a Full Scram h. 400000 A4.01 - Component Cooling Water
ES 301,Page 22 of 27
/ Verity Proper Isolation of (PLOR-004C) - SET 2 Reactor Building Closed Cooling Water (RBCCW) (2005 NRC) - SET 3 I b. I D, EN, L, S 7 ! D, P, S 8 I! -I! I I I I 1 In-Plant Systems@
 
(3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) j. 217000 A2.04 - Reactor Core Isolation Cooling / Defeat Auto Open Signal of RClC Torus Suction Valves - Unit 2 (NEW - AC) 13.3-2 k. 295028 EA1.03 - Drywell Chilled Water Low Level (Alternate Path - Manual Makeup to Drywell Chilled Water System) - Unit 2 (NEW - ARC A, E, N, R 217 H-5) @ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may *Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power I Shutdown (N)ew or (M)odified from bank including 1 (A) (P)revious 2 exams (WCA (S)imulator ES-30 4-6 I 4-6 I 2 <9 158 I54 - >I I? 11 ,I - >I 121 121 - >2 122 1'1 - >I 1'1 121 - I - I 2 1 (control room system) - < 3 I 5 3 I 5 2 (randomly selected)  
ES-301                                Control Room/ln-Plant Systems Outline                      Form ES-301-2 Facility: Peach Bottom                                            Date of Examination: 12/08/2008 Exam Level: RO            SRO-I 0 SRO-U 0                          Operating Test Number: 2008 NRC System / JPM Title                              Type Code*          Safety Function
~ I/ Ege 23 of 27 Scenario Outline ES-8-1 It Event No. 1 11 Simulation Facility Peach Bottom Scenario No. #I (altered bank) Op Test No. 2008 NRC; Malfunction Event Event N URO SwapCRDpumps No. Type* Description CRS 11 Examiners Operators CRS (:SRO) 6 URO 4TC) C URO CRS PRO (30P) 7 Scenario Summary The scenario begins with a plant startup in progress at approximately 5% power following a refueling outage. During shift turnover, the crew is directed to swap CRD pumps due to a noisy bearing on the 'A pump. Following the CRD pump swap, the 'B' drywell chiller trips, requiring the crew to place the standby drywell chiller in service in accordlance with ON-I20 "High Drywell Temperature".
: a. 202001 A4.01 - Recirculation System / Start a Recirc IPump (Alternate Path - Scoop Tube Lockup) (PLOR-309CA) - SET     ~. 4
Next, a loss of MCC E224-R-B results in a loss of the 'B' RPS MG set, a half scram and PClS outboard Group II isolation. The crew will investigate, transfer RPS to the alternate supply and reset the half scram and PClS isolation. Following the Tech Spec evaluation, startup level controller LCV- 8091 will fail open, requiring the crew to rrianually restore and control RPV water level in accordance with OT-I 10 "Reactor High Level". This event is further complicated by an inadvertent RClC initiation, requiring entry into OT-104 "Positive Reactivity Insertion" and manual shutdown of RCIC. Following this, an EHC failure will cause reactor pressure to rise, requiring entry into OT-102 "Reactor High Pressure".
: b. 295031 EA1.02 - High Pressure Coolant Injection / Manually Initiate HPCI (Alternate Path - Manual Initiation Pushbutton F,ailsTo Operate)
The crew will be? unable to reduce reactor pressure. The reactor will fail to automatically scram on high pressure and the crew will be required to insert a manual scram.
(2007 NRC / PLOR-300CA) - SET 1
Shortly after the scram, a leak will develop in the t.orus, requiring the crew to enter T-103 "Secondary Containment Control" and T-I 02 "Primary Containment Control".
: c. 239001 A4.01 - Main Steam System / Open Main Steam Isolation Valves After a Group-1 Isolation (PLOR-083C) - SET 2
A turbine bypass valve (#I) will fail (remain) open and, due to a failure of the inode switch, will result in MSlVs closing when reactor pressure decreases below 850 psig.
: d. 209001 A4.04 - Core Spray System I Perform Pump Capacity Test For                A, L, M, S          4 IST (Alternate Path - Minimum Flow Valve Fails To Open) - SET 3
As torus level continues to drop, the crew will be required to perform T-I 12 "Emergency Blowdown".
: e. 223002 A4.03 - Primary Containment Isolation System / Perform a                    D, EN, S            5 Group I PClS Isolation Reset (GP-8A) (PLOR-024C) - SET 1
M ALL Torus leak iiito secondary containment (torus room) leading to emergency blowdown / turbine bypass valve fails open, causing MSlVs to close (due to failed mode switch) 41 -! C PRO CRS C URO TS PRO CRS I URO CRS I PRO TS CRS Drywell chiller trip Loss of MCC E224-R-B resulting in half scram and Group II outboard isolation I transfer RPS power supplies, reset half scram and isolations Startup level controller (LCV-8091) failure Inadvertent RClC initiation EHC failure causes rising reactor pressure / reactor scram with mode switch failurle (manual scram works)
: f. 262001 A4.04 - AC Distribution / Excite The Main Generator                            D, s              6 (PLOR-031C) - SET 4
Scenario Outline ES-R3-1 I, 2 11 Simulation Facility Peach Bottom Scenario No. #2 (altered bank) Op Test No. 2008 NR( : ~~~ ~ C URO CRS TBCCW pump trip w/ failure of standby pump to auto-start 11 Examiners C PRO TS CRS Operators CRS ('3RO) SRV inadvertently opens, requiring torus cooling to be maximized
: g. 212000 A4.14 - Reactor Protection System / Reset a Full Scram                    D, EN, L, S            7 (PLOR-004C) - SET 2
/ SRV closes when control power fuses are removed URO I ATC) PRO (30P) 4 5 6 Scenario Summary The scenario begins with the reactor at approximately 76% power with power ascension on hold. The crew will perform ST-0-001 -200-2 "Turbine Stop Valve Closure and EOC-RPT Functional Test" when an RPS failure will require the crew to make a Tech Spec declaration. This will be followed by a trip of the in-service TBCCW pump with a failure of the standby pump to auto-start. The crevt' will be required to respond IAW ON-1 18 "Loss of TBCCW and place the standby TBCCW pump in service. Following this, the
: h. 400000 A4.01 - Component Cooling Water I Verify Proper Isolation of                D,p, s              8 Reactor Building Closed Cooling Water (RBCCW) (20135 NRC) - SET 3
'A SRV will inadvertently open, requiring the crew to take actions IAW OT-I14 "Inadvertent Opening of a Relief Valve".
: i. 295037 G2.4.35 - Control Rod Drive Hydraulic Systerri / Isolate And Vent          D, E, L, R          1 The Scram Air Header - Unit 3 (PLOR-074P)
Power will be reduced in accordance with GP-9-2 "Fast Power Reduction". The crew will be successful in closing the  
: j. 217000 A2.04 - Reactor Core Isolation Cooling / Defeat Auto Open Signal            E, N, R            2 of RClC Torus Suction Valves - Unit 2 (NEW - A 0 13.:3-2)
'A SRV by directing plant operators to pull fuses for the valve.
: k. 295028 EA1.03 - Drywell Chilled Water Low Level (Alternate Path -                 A, E, N, R          5 Manual Makeup to Drywell Chilled Water System) - Unit 2 (NEW - ARC
R URO Fast power reduction due to SRV opening CRS ALL "- M Steam leak in the primary containment
                        *Type Codes                              Criteria for RO I SRO-I I SRO-U (A)lternate path                                                      4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank                                                    -
/ hydraulic ATWS
                                                                          <9  I58 I 5 4 (E)mergency or abnormal in-plant                                      -
/ pressrrre instrument f<ailure prevents using containment sprays Standby liquid control pump trips requiring manual start of the C URO CRS alternate pump A small steam leak inside the primary containment will occur next. The crew will be required to take actions in accordance with OT-101 "High Drywell Pressure". When the reactor is scrammed, a hydraulic ATWS will occur, requiring the cirew to enter T-101 "RPV Control" and T-I 17 "LeveVPower Control". A failure of the Standby Liquid Control pump will require the crew to start the other pump in order to successfully lower reactor power. The crew will also be required to enter T-102 "Primary Containment Control" due to high drywell pressure. After diagnosing the inability to spray the containment due to an instrument failure, the crew will perform T-I12 "Emergency Blowdown". One ADS SRV will fail to open, requiring the opening of another SRV. The crew will need to implement T-216 "Control Rod Insertion By Manual Scram Or Individual Scram Test Switches" and T-220 "Driving Control Rods During Failure To Scram" to terminate the ATWS. 7 Initial IC-72, 76% power Conditions Turnover See Attached "Shift Turnover" Sheet I PRO CRS ADS SRV fails to open during emergency blowdown requiring an additional SlRV to be opened Event Event Description main turbine stop valve functional test
                                                                          > I  I > 1/>1 (EN)gineered safety feature                                            - I - I 2 1 (control room system)
/ RPS failure during Scenario Outline ES-13-1 Event No. 1 2 Simulation Facility Peach Bottom Scenario Nlo. #3 (modified bank)
(L)ow-Power I Shutdown                                                -
Op Test No. 2008 NR( Malfunction Event Event No. Type* Description
                                                                          > I  1 1 1 121 (N)ew or (M)odified from bank including 1(A)                          -
-- N PRO Perform HFCI surveillance testing CRS URO CRS C Service Water pump trip, requiring manual start of standby pump Examiners 3 4 5 Operators CRS ( SRO) C PRO HPCl cooling water leak requires HPCl shutdown TS CRS TS CRS R URO CRS Loss of DC power to RPS MG set output breaker Condensate pump trip with recirc runback failure / power reduction URO ATC) 7 8 PRO I BOP) ~ C URO CRS I PRO CRS Scenario Summary The scenario begins with the reactor at 95% power. Immediately after shift turnover the crew will commence the HPCl functional and in-service test. While the test is in progress, the running Service Water pump will trip on overcurrent, requiiring the crew to place the standby pump in service using the system operating procedure. The crew will then receive a report from the field of a HPCl system cooling water leak, requiring HPCl to be shutdown and declared inoperable.
22  I > 2 I 21 (P)revious 2 exams                                                    < 3 I 5 3 I 5 2 (randomly selected)
Next, a loss of DC: power to an in-service RPS MG set output breaker will occur, requiring application of the appropriate Tech Spec. When this is complete, the 'A,' Condensate pump will trip without the expected Recirc System runback.
                                                                          -
Power must be manually reduced using recirc flow to prevent a low-level scram. When conditions have stabilized, #2 Auxiliary Bus will trip on overcurrent, removing the remaicing Condensate pumps from service.
(WA                                                                  > I I >I
An RPS failure will prevent the automatic and manual scrams, requiring entry into T-101 "RPV Control", T-117 "LeveVPower Control", and the use of Alternate Rod Insertion (ARI) to shutdown the reactor. The scram discharge volume will fail to completely isolate and must be manually isolated. RClC will trip when either started manually or automatically, which will remove the final source of high pressure feed. As level deteriorates, the crew should start available low pressure ECCS pumps and when the crew determines level cannot be restored and maintained above -195 inches, the reactoir will be depressurized in accordance with T-I 12 "Emergency Blowdown", after terminating and preventing injection per T-240 (due to the six-rod ATWS). Low pressure ECCS will be available to recover reactor level.
                                                                          -          121 I  (S)imuiator 1                                            1                              1                                      1 ES-301, Page 23 of 27
I ALL Loss of #2 auxiliary bus / loss of condensate
 
& feedwater
ES-301                              Control Room/ln-Plant Iivstems Outline                    Form ES-301-2
/ RClC trips on over-speed during startup and cannot be reset RPS failure requires ARI initiation to scram the reactor / ATWS (six control rods) requires terminating and preventing injection before emergency depressurization
___
~~ ~ ~~ Two in-series scram discharge volume (SDV) vent valves fail to automatically isolate I I I * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS) Tech Spec Scenario Outline ES-11-1 Simulation Facility Peach Bottom Scenario No. #4 (altered bank) Op Test No. 2008 NRC: Examiners Operators CRS (3RO) URO 1 ATC) PRO I BOP) SPARE Scenario The scenario begins with the reactor at 82% power and a plant shutdown in progress. The crew will lower reactor power using reactor recirculation flow and once below 80% power, the crew will secure a condensate pump. Following the condensate pump shutdown, the 2SU-E feeder will trip.
Facility: Peach Bottom                                            Date of Examination: 12/08/2008 Exam Level: RO 0 SRO-I                SRO-U 0                    Operating Test Number: 2008 NRC Control Room Systems@(8 for RO); (7 for SRO-I); (2 or :3 for SRO-U, including 1 ESF)
Tt-e E12 bus will not fast transfer to the other startup feed, causing the E-I diesel to start and its breaker to automatically close onto the bus Automatic cooling to the diesel will not occur, requiring the crew to establish cooling manually. The crew will be required to make a Tech Spec declaration for the electrical failure. Scenario Summary Event No. 1 2 This will be followed by a trip of the 'B' rec:irc pump due to a failed RPT breaker. The crew should carry out the actions of OT-I 12 "Unexplained/Unexpected Change in Core Flow", which includes establishing single loop operation and corisulting Technical Specifications. A loss of offsite power will occur next, requiring entry into SE-11 "Lo!ss of Off-Site Power". The crew should stabilize plant parameters using T-100 "Scram" and should recognize and respond to a failure of the HPCl flow controller to operate in automatic. The E-4 diesel generator will fail to automatically start, and the E-3 diesel generator will not start at all. The crew will be required to manually start the E-4 diesel generator using the quick-start pushbutton in order to spray the Drywell later in the scenario.
I/                                     System / JPM Title 1                I  Safety Function
Malfunction Event Event No. Type* Description R URO Lower reactor power with reactor recirculation flow CRS N PRO Secure a condensate pump CRS Following this event, a steam leak will develop in the drywell, requiring the crew to take actions in accordance with OT-101 "High Drywell Pressure", and execute T-101 "RPV Control" and T-10% "Primary Containment Control". The high drywell pressure condition will prevent HPCl from being used to control reactor pressure, resulting in further challenge to the primary containment.
                                                                                                              ~
C URO TS CRS Recirc RPI- breaker trip
: a. 202001 A4.01 - Recirculation System / Start a Recirc IPump (Alternate              A, D, S           1 Path - Scoop Tube Lockup) (PLOR-309CA) - SET 4
/ single loop operation I3l 7 I URO HPCl flow (controller fails in automatic CRS - Loss of 2SlU-E startup feed with failure of the E12 bus to fast transfer
: b. 295031 EA1.02 - High Pressure Coolant Injection / Manually Initiate              A, D, EN,           2 HPCl (Alternate Path - Manual Initiation Pushbutton F,ailsTo Operate)             L, P, s (2007 NRC / PLOR-300CA) - SET 1                  ____.
/ El EDG auto starts with failure of ESW cooling to diesel auxiliaries I1 I I M ALL I Loss of off-site power / steam leak in the drywell II I PRO E-4 diesel
: c. 239001 A4.01 - Main Steam System / Open Main Steam Isolation Valves                D, L, S            3 After a Group-I Isolation (PLOR-083C) - SET 2
!generator fails to auto start I CRS I}}
: d. 209001 A4.04 - Core Spray System / Perform Pump Capacity Test For                A, L, M, S          4 IST (Alternate Path - Minimum Flow Valve Fails To Open) - SET 3
: e. 223002 A4.03 - Primary Containment Isolation Systern I Perform a                  D, EN, S            5 Group I PClS Isolation Reset (GP-8A) (PLOR-024C) - SET 1 f.
: g. 212000 A4.14 - Reactor Protection System / Reset a Full Scram                    D, EN, L, S (PLOR-004C) - SET 2
: h. 400000 A4.01 - Component Cooling Water / Verify Proper Isolation of Reactor Building Closed Cooling Water (RBCCW)
In-Plant Systems@(3 for RO); (3 for SRO-I); (3 or 2 for SIRO-U)
                        *Type Codes                              Criteria for RO I SRO-I I SRO-U (A)lternate path                                                      4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank                                                    -
                                                                          < 9 1 5 8 I54 (E)mergency or abnormal in-plant                                      -
                                                                          > I I > 1 1 21 (EN)gineered safety feature                                            - I - I 2 1 (control room system)
(L)ow-Power I Shutdown                                              -
                                                                          >I  1>1121 (N)ew or (M)odified from bank including 1(A)                          -
                                                                          > 2 I > 2 I 21 (P)revious 2 exams                                                  < 3 I 5 3 I 5 2 (randomly selected)
                                                                          -
(WCA                                                                > I I> I 1 2 1
                                                                          -
(S)imulator I
 
ES-301                               Control Roomlln-Plant Svstems Outline                               Form ES-301-2 Facility: Peach Bottom                                                   Date of Examination: 12/08/2008 Exam Level: RO 0 SRO-I 0 SRO-U [XI                                       Operating Test Number: 2008 NRC II/ Control Room Systems@(8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
Safety System / JPM Title Type 'Ode*      Function I  b.                                                                                         I                I I                I            !
: d. 209001 A4.04 - Core Spray System / Perform Pump Capacity Test For                            A, L, M, S        4    1 Open) - SET 3                                                1 1s 1;
: f.                                                                                                                        I
: g. 212000 A4.14 - Reactor Protection System I Reset a Full Scram                              D, EN, L, S       7 (PLOR-004C) - SET 2                                                                                                  !
: h. 400000 A4.01 - Component Cooling Water / Verity Proper Isolation of                          D, P, S         8       I!
Reactor Building Closed Cooling Water (RBCCW) (2005 NRC) - SET 3 1 In-Plant Systems@(3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
                                                                                                                            -I!
: j. 217000 A2.04 - Reactor Core Isolation Cooling / Defeat Auto Open Signal of RClC Torus Suction Valves - Unit 2 (NEW - AC) 13.3-2
: k. 295028 EA1.03 - Drywell Chilled Water Low Level (Alternate Path -                           A, E, N, R Manual Makeup to Drywell Chilled Water System) - Unit 2 (NEW - ARC 217 H-5)
      @         All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may
                        *Type Codes                                     Criteria for RO / SRO-I / SRO-U (A)lternate path                                                             4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank                                                           -< 9 1 5 8 I 5 4 (E)mergency or abnormal in-plant                                             ->I  I ? 11 ,  I (EN)gineered safety feature                                                     - I - I 2 1 (control room system)
(L)ow-Power IShutdown                                                        ->I1 2 1 1 2 1 (N)ew or (M)odified from bank including 1(A)                                 -> 2 1 2 2 1 ' 1 (P)revious 2 exams                                                           -< 3 I 5 3 I 5 2 (randomly selected)
(WCA                                                                         ->I  1'1 121 (S)imulator ES-30 E g e 23 of 27 I/~
 
Scenario Outline                                        ES-8-1 1
It Simulation Facility Peach Bottom              Scenario No.      # I (altered bank)    Op Test No. 2008 NRC; 1 Examiners                                                        Operators                              CRS (:SRO)
URO 4TC)
PRO (30P)
Scenario     The scenario begins with a plant startup in progress at approximately 5% power following a refueling Summary      outage. During shift turnover, the crew is directed to swap CRD pumps due to a noisy bearing on the A pump. Following the CRD pump swap, the B drywell chiller trips, requiring the crew to place the standby drywell chiller in service in accordlance with ON-I20 High Drywell Temperature.
Next, a loss of MCC E224-R-B results in a loss of the B RPS MG set, a half scram and PClS outboard Group II isolation. The crew will investigate, transfer RPS to the alternate supply and reset the half scram and PClS isolation. Following the Tech Spec evaluation, startup level controller LCV-8091 will fail open, requiring the crew to rrianually restore and control RPV water level in accordance with OT-I 10 Reactor High Level. This event is further complicated by an inadvertent RClC initiation, requiring entry into OT-104 Positive Reactivity Insertion and manual shutdown of RCIC.
Following this, an EHC failure will cause reactor pressure to rise, requiring entry into OT-102 Reactor High Pressure. The crew will be?unable to reduce reactor pressure. The reactor will fail to automatically scram on high pressure and the crew will be required to insert a manual scram. Shortly after the scram, a leak will develop in the t.orus, requiring the crew to enter T-103 Secondary Containment Control and T-I 02 Primary Containment Control. A turbine bypass valve (#I) will fail (remain) open and, due to a failure of the inode switch, will result in MSlVs closing when reactor pressure decreases below 850 psig. As torus level continues to drop, the crew will be required to perform T-I 12 Emergency Blowdown.
Event      Malfunction            Event                                          Event No.           No.               Type*                                      Description 1                            N    URO      SwapCRDpumps CRS C      PRO    Drywell chiller trip CRS C    URO      Loss of MCC E224-R-B resulting in half scram and Group II outboard TS    PRO      isolation I transfer RPS power supplies, reset half scram and isolations CRS 4  1                          I   URO      Startup level controller (LCV-8091) failure
  -                                            !
CRS I    PRO    Inadvertent RClC initiation TS      CRS 6                            C    URO      EHC failure causes rising reactor pressure / reactor scram with mode CRS    switch failurle (manual scram works) 7                            M      ALL    Torus leak iiito secondary containment (torus room) leading to emergency blowdown / turbine bypass valve fails open, causing MSlVs to close (due to failed mode switch)
 
Scenario Outline                                        ES-R3-1 1
I, Simulation Facility Peach Bottom            Scenario No.      #2 (altered bank)     Op Test No.      2008 NR( :
1  Examiners                                                      Operators                                CRS (3RO)
URO I ATC)
PRO (30P)
Scenario    The scenario begins with the reactor at approximately 76% power with power ascension on hold.
Summary      The crew will perform ST-0-001-200-2 Turbine Stop Valve Closure and EOC-RPT Functional Test when an RPS failure will require the crew to make a Tech Spec declaration. This will be followed by a trip of the in-service TBCCW pump with a failure of the standby pump to auto-start. The crevt will be required to respond IAW ON-118 Loss of TBCCW and place the standby TBCCW pump in service. Following this, the  ASRV will inadvertently open, requiring the crew to take actions IAW OT-I14 Inadvertent Opening of a Relief Valve. Power will be reduced in accordance with GP-9-2 Fast Power Reduction. The crew will be successful in closing the  ASRV by directing plant operators to pull fuses for the valve.
A small steam leak inside the primary containment will occur next. The crew will be required to take actions in accordance with OT-101 High Drywell Pressure. When the reactor is scrammed, a hydraulic ATWS will occur, requiring the cirew to enter T-101 RPV Control and T-I 17 LeveVPower Control. A failure of the Standby Liquid Control pump will require the crew to start the other pump in order to successfully lower reactor power.
The crew will also be required to enter T-102 Primary Containment Control due to high drywell pressure. After diagnosing the inability to spray the containment due to an instrument failure, the crew will perform T-I12 Emergency Blowdown. One ADS SRV will fail to open, requiring the opening of another SRV. The crew will need to implement T-216 Control Rod Insertion By Manual Scram Or Individual Scram Test Switches and T-220 Driving Control Rods During Failure To Scram to terminate the ATWS.
Initial      IC-72, 76% power Conditions Turnover      See Attached Shift Turnover Sheet Event                                      Event Description main turbine stop valve functional test / RPS failure during
                                ~~~            ~
2                            C    URO    TBCCW pump trip w/ failure of standby pump to auto-start CRS C    PRO    SRV inadvertently opens, requiring torus cooling to be maximized /
TS    CRS    SRV closes when control power fuses are removed 4                              R    URO    Fast power reduction due to SRV opening CRS
                                                                                                                    -
5                            M    ALL    Steam leak in the primary containment / hydraulic ATWS / pressrrre instrument f<ailureprevents using containment sprays 6                              C    URO    Standby liquid control pump trips requiring manual start of the CRS    alternate pump 7                              I   PRO     ADS SRV fails to open during emergency blowdown requiring an CRS    additional SlRV to be opened
 
Scenario Outline                                         ES-13-1 Simulation Facility Peach Bottom             Scenario Nlo.     #3 (modified bank)     Op Test No. 2008 NR(
Examiners                                                       Operators                                 CRS ( SRO)
URO ATC)
PRO I BOP)
Scenario      The scenario begins with the reactor at 95% power. Immediately after shift turnover the crew will Summary      commence the HPCl functional and in-service test. While the test is in progress, the running Service Water pump will trip on overcurrent, requiiring the crew to place the standby pump in service using the system operating procedure. The crew will then receive a report from the field of a HPCl system cooling water leak, requiring HPCl to be shutdown and declared inoperable. Next, a loss of DC:
power to an in-service RPS MG set output breaker will occur, requiring application of the appropriate Tech Spec. When this is complete, the A, Condensate pump will trip without the expected Recirc System runback. Power must be manually reduced using recirc flow to prevent a low-level scram.
When conditions have stabilized, #2 Auxiliary Bus will trip on overcurrent, removing the remaicing Condensate pumps from service. An RPS failure will prevent the automatic and manual scrams, requiring entry into T-101 RPV Control, T-117 LeveVPower Control, and the use of Alternate Rod Insertion (ARI) to shutdown the reactor. The scram discharge volume will fail to completely isolate and must be manually isolated. RClC will trip when either started manually or automatically, which will remove the final source of high pressure feed. As level deteriorates, the crew should start available low pressure ECCS pumps and when the crew determines level cannot be restored and maintained above -195 inches, the reactoir will be depressurized in accordance with T-I 12 Emergency Blowdown, after terminating and preventing injection per T-240 (due to the six-rod ATWS). Low pressure ECCS will be available to recover reactor level.
Event      Malfunction            Event                                          Event No.          No.                Type*                                      Description                        -
1                              N    PRO      Perform HFCI surveillance testing CRS 2                            C    URO      Service Water pump trip, requiring manual start of standby pump CRS 3                              C    PRO      HPCl cooling water leak requires HPCl shutdown TS    CRS 4                            TS    CRS      Loss of DC power to RPS MG set output breaker 5                              R    URO      Condensate pump trip with recirc runback failure / power reduction CRS 7
I  C ALL URO
                                            ~
Loss of #2 auxiliary bus / loss of condensate & feedwater / RClC trips on over-speed during startup and cannot be reset RPS failure requires ARI initiation to scram the reactor / ATWS (six CRS      control rods) requires terminating and preventing injection before emergency depressurization
                                                            ~        ~~          ~~
8                              I    PRO      Two in-series scram discharge volume (SDV) vent valves fail to CRS      automatically isolate I                    I              I
* (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS) Tech Spec
 
Scenario Outline                                           ES-11-1 Simulation Facility Peach Bottom             Scenario No.       #4 (altered bank)     Op Test No.     2008 NRC:
Examiners                                                       Operators                                 CRS (3RO)
URO ATC) 1 PRO I BOP)
SPARE Scenario Scenario    The scenario begins with the reactor at 82% power and a plant shutdown in progress. The crew will Summary      lower reactor power using reactor recirculation flow and once below 80% power, the crew will secure a condensate pump. Following the condensate pump shutdown, the 2SU-E feeder will trip. Tt-e E12 bus will not fast transfer to the other startup feed, causing the E-I diesel to start and its breaker to automatically close onto the bus Automatic cooling to the diesel will not occur, requiring the crew to establish cooling manually. The crew will be required to make a Tech Spec declaration for the electrical failure.
This will be followed by a trip of the B rec:irc pump due to a failed RPT breaker. The crew should carry out the actions of OT-I 12 Unexplained/UnexpectedChange in Core Flow, which includes establishing single loop operation and corisulting Technical Specifications. A loss of offsite power will occur next, requiring entry into SE-11 Lo!ss of Off-Site Power. The crew should stabilize plant parameters using T-100 Scram and should recognize and respond to a failure of the HPCl flow controller to operate in automatic. The E-4 diesel generator will fail to automatically start, and the E-3 diesel generator will not start at all. The crew will be required to manually start the E-4 diesel generator using the quick-start pushbutton in order to spray the Drywell later in the scenario.
Following this event, a steam leak will develop in the drywell, requiring the crew to take actions in accordance with OT-101 High Drywell Pressure, and execute T-101 RPV Control and T-10%
Primary Containment Control. The high drywell pressure condition will prevent HPCl from being used to control reactor pressure, resulting in further challenge to the primary containment.
Event    Malfunction            Event                                          Event No.          No.                Type*                                      Description 1                            R    URO      Lower reactor power with reactor recirculation flow CRS 2                            N    PRO      Secure a condensate pump CRS I3l                                              Loss of 2SlU-E startup feed with failure of the E12 bus to fast transfer /
E l EDG auto starts with failure of ESW cooling to diesel auxiliaries 1I I                              TS C    URO CRS Recirc RPI- breaker trip / single loop operation I        I                    I  M    ALL    I Loss of off-site power / steam leak in the drywell I        PRO CRS    I E-4 diesel !generatorfails to auto start 7                             I   URO     HPCl flow (controllerfails in automatic CRS
  -}}

Revision as of 11:18, 14 November 2019

Draft - Outlines (Folder 2)
ML083540094
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Site: Peach Bottom  Constellation icon.png
Issue date: 07/24/2008
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Text

'acility Name: Peach Bottom Date of Extam:12/08/2008 SRO-Onlv Points A2 I G* I Total

-,*

lote 1.

I*

Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (Le., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each WA category shall not be less than two).

2. The point total for each group and tier in the proposed outline must match that specified in the table.

The final point total for each group and tier may deviate! by +I from that specified in the table based on NRC revisions. The fiial RO exam must total 75 points and the SRO-only exam must total 25 points.

3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to Section D.l .b of ES-401 for guidance regarding the elimination of inappropriate WA statements.
4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before select,n$

a second topic for any system or evolution.

5. Absent a plant-specific priority, only those WAS having an importance rating (IR) of 2.5 or higher shall be selected.

Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6. Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories.

7.* The generic (G) WAS in Tiers Iand 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.l .b of ES-401 for the applicable WAS.

a. On the following pages, enter the WA numbers, a brief description of each topic, the topics' importance ratings (IRs) for the applicable license level, and the point totals (#) lor each system and category. Enter the group and tier totals for each category in the table above; if fuel handling eqiuipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note # I does not apply). Use duplicate pages for RO and SRO-only exams.
9. For Tier 3, select topics from Section 2 of the WA catalog, and enter the WA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to WAS that are linked to 10 CFR 55.43.

ES-401, Page 17 of 34

ES-401 2 Form ES-40I-I

-

ES-401 BWR Examination Outline Form ES-41 1-I1 Em lency and Abnormal Plant Evolutions -Tier IIGroup 1 (RO)

1) EIAPE # I Name I Safety Function l 295001 Partial or Complete Loss of Forced Core Flow Circulation I 1 & 4 295003 Partial or Complete Loss of AC I 6 295004 Partial or Total Loss of DC Pwr I 6 295005 Main Turbine Generator Trip I 3 11295006 SCRAM I 1 11295016 Control Room Abandonment I 7 295018 Partial or Total Loss of CCW I 8 295019 Partial or Total Loss of Inst. Air I8 295021 Loss of Shutdown Cooling I 4 295023 Refueling Acc I 8 295024 High Drywell Pressure I 5 1 295025 High Reactor Pressure I 3 295027 High Containment Temperature I 5 1I I---

295028 High Drywell Temperature I 5 295030 Low Suppression Pool Wtr Lvl I 5

~~

295031 Reactor Low Water Level I 2 295037 SCRAM Condition Present Reactor Power Above APRM Downscale or 295038 High Off-site Release Rate I 9 600000 Plant Fire On Site I 8 Disturbances I 6

~ -

11WA Category Totals:

ES-401 3

-

Form ES-404 -1

~~ ~~

ES-401, Page 19 of 34

ES-401 4 Form ES-401-1 IlES-401 BWH Examination Outline Form ES-401-1 ES-401,Page 20 of 34

ES-401-1 5 Form ES-401-1 ES-401, Page 22 of 34

~~

ES-401 2 Form ES-401-1

-

ES-401 BWR Examination Outline Form ES-4C 1 -

95025 High Reactor Pressure / 3 Containment conditionslisolations 295038 High Off-site Release Rate / 9 00000 Plant Fire On Site / 8 or Voltage and Electr

ES-401 3 -

Form ES-40"11 ES-401,Page 19 of 34

ESQOI 4 Form ES-401-1 ES-401, Page 20 of 34

ES-401 5 Form ES-401-1 6 ES-401 BWR IExamination Outline Form ES-401-1 Plant Svsterns - Tier 2/GrOUD 2 (SRO)

ES-401,Page 21 of 34

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3

-1  ?:Peach Bottom Date of Exam:12/0~3/2008 Category KIA # Topic RO I SRO-Only I R ) # I I R I #

2.1. 01 IKnowledgeof conduct of operations requirements Knowledge of individual licensed operator responsibilitiesrelated to shift staffing, such as 13.81 I I 2.1. 04 medical requirements. "no-solo"operation, mainte-lance of active license status 3.3 1 10CFR55, etc 1.

2.1. 17 IAbiIity to make accurate, clear, and concise verbal reports 13.91 1 I I Conduct of Knowledge of procedures, guidelines. or limitationsassociated with reactivity 2.1. 37 management 4.6 1 Operations Ability to identify and interpret diverse Sndications IQ validate the response of another

2. . 45 indicator 4.3 1 2.1.

Subtotal Ability to determine the expected plant configurationusing design and configuration 2.2. control documentation, such as drawings, line-ups tag-Outs. etc 3.9 1 I

2.2. 2 1 (Knowledgeof pre- and post-maintenance operabi1Ml.y requirements I 2.9 I I

2. 3.8 1 Equipment Control 2.2. I 2.2.

Subtotal IKnowledaeof radioloaical safetv orinciDles Dertaini L .

2.3. 12 containmh entry re&rements fuel handling responsibilities access lo locked high- 3.2 1 radiation areas. alianina filters. etc Knowledge of radiation or contarnination hazards that may arise during normal abnormal 2'3. or emergency conditions or activities 34 1 Knowledge of radiologicalsafety procedures pertaining to licensed operator duties such 2.3. 13 as response to radiation monitor alarms containment entry requirements, fuel handling 3.8 1

3. reSDOnSibilitieS.access to locked hiah-radiationareas. alianina filters. etc Radiation Control
  • 3. Knowledge of radiation or contamination hazards thal may arise during normal abnormal or emergency conditions or activities I

38 1 2.3. I 2.3.

Subtotal Knowledge of the bases for prioritizing safety functi 2.4. 22 operations Knowledge of RO tasks performed outside the mairi control room during an emergency

'2.4. 341and the resultant ODerational effects I 4.2 I 1 I

4. 4.1 1 Emergency Procedures 4.5 1 I Plan 2.4. 45 IAbility to prioritize and interpret the significanceof f?achannunciator or alarm I

I I I 4.3 I 1 2.4.

I Subtotal Tier 3 Point rota1 ES-401, Page 27 of 34

ES-401 Record of Rejected WAS Form ES-401-4 Randomly Tier /

Selected Reason for Rejection Group WA Q#46 295019 At Peach Bottom, there is no impact on RHRlLPCl from loss of instrument RO1/1 AK2.19 air other than the inabiliity to manually stroke testable check valves.

(Replaced with 295019 AK2.05)

Q#48 295023 Unable to construct anRO question for this WA that meets the ROIII 2.2.42 requirements of NUREG-1021.

(Replaced with 295023 2.4.31)

Q#52 295028 Application of Technical Specifications is not an RO job function.

RO1/1 2.4.40 (Replaced with 295028 2.2.22)

Q#57 600000 Unable to construct an RO question for this WA that meets the RO1/1 AK1.01 requirements of NUREG-1021.

(Replaced with 600000 AKI .02)

Q#65 295036 Unable to construct an RO question for this WA that meets the RO1/2 EK2.02 requirements of NUREG-1021.

(Replaced with 295036 EK2.01)

Q#5 209001 Unable to construct anRO question for this WA that meets the RO2/1 K3.03 requirements of NUREG-1021.

(Replaced with 209001 K3.02)

Q#8 215003 Unable to construct an RO question for this WA that meets the RO2/1 K1.04 requirements of NUREG-1021.

(Replaced with 215003 K1.02)

Q#l7 261000 Unable to construct an RO question for this WA that meets the RO2/1 K6.09 requirements of NUREG-1021.

(Replaced with 261000 K6.03)

Q#23 263000 Unable to construct an RO question for this WA that meets the RO2/1 2.4.18 requirements of NUREG-1021.

(Replaced with 263000 2.1.23)

Q#33 226001 At Peach Bottom, there are no automatic operations associated with the RO212 A3.02 Containment Spray mode of RHR/LPCI based on system pressure.

(Replaced with 226001 A3.01)

Q#37 245000 Unable to construct an RO question for this WA that meets the RO2/2 2.2.39 requirements of NUREG-1021.

(Replaced with 245000 2.1.20)

Q#79 261000 There are no conditions and limitations in the facility license associated SRO2/1 2.2.38 with the Standby Gas Treatment System.

(Replaced with 261000 2.2.40)

Q#85 295016 Unable to construct an SRO question for this WA that meets the SRO 1 / 1 A42.07 requirements of NUREG-1021.

(Replaced with 295016 AA2.06)

ES-401, Page 27 of 33

,

ES-301 Administrative ToDics Outline Form ES-301-1 Facility: Peach Bottom Date of Examination: 12/08/2008 Examination Level: RO SRO 0 Operating Test Number: 2008 NRC Administrative Topic TYPe Describe activity to be performed (See Note) Code-*

G2.1.29 - Lineup Standby Gas Treatment System For Conduct of Operations N. S Automiatic Operation (New - SO 9A. 1.A COL)

Conduct of Operations Not Required G2.2.41 - Isolate the 2A Turbine Building Closed Cooling Equipment Control N, R Water IPump Due to a System Leak (New - P&ID M-316)

G2.3.11 - Perform PRO Duties For A Liquid Radwaste Radiation Control Dischairge (2001 NRC)

G2.4.3!3 - Activate The Emergency Response Data Emergency Plan D. S Systerrt (PLOR-186C)

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

  • Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (53 for ROs; 5 4 for SROs & RO retakes)

(N)ew or (M)odifiied from bank (2 1)

(P)revious 2 exams (5 1; randomly selected)

ES 301,Page 22 of 27

-_____

ES-301 Administrative Topics Outline Form ES-301-1

,

Facility: Peach Bottom Date of Examination: 12/08/2008 Examination Level: RO SRO Operating Test Number: 2008 NRC Administrative Topic TYPe Describe activity to be performed (See Note) Code*

Conduct of Operations G2.1.34 - Review And Evaluate Reactor Coolant System Chemistry Limits - Condenser Tube Leak at Power (New - CH-10, ON-126, TRM 3.9)

~ ~

Conduct of Operations N. R G2.1.26 - Determine Minimum Required Personal Protective Equipment For Racking Out A 480 Volt Breaker (New - SA-AA-129)

Equipment Control D, R G2.2.6 - Review And Approve A Temporary Procedure Change (PLOR-222C)

Radiation Control G2.3.1:3 - Review And Approve Primary Containment PurgeNent Isolation Valve Cumulative Hour Log (2007 NRC)

~

Emergency Plan G2.4.40 - Make EAL Classification And State/Local Notifications For ALERT - High Winds With Visible Plant Damage (PLOR-234C)

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

  • Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (53 for ROs; 5 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (2 1)

(P)revious 2 exaims (5 1; randomly selected)

ES 301,Page 22 of 27

ES-301 Control Room/ln-Plant Systems Outline Form ES-301-2 Facility: Peach Bottom Date of Examination: 12/08/2008 Exam Level: RO SRO-I 0 SRO-U 0 Operating Test Number: 2008 NRC System / JPM Title Type Code* Safety Function

a. 202001 A4.01 - Recirculation System / Start a Recirc IPump (Alternate Path - Scoop Tube Lockup) (PLOR-309CA) - SET ~. 4
b. 295031 EA1.02 - High Pressure Coolant Injection / Manually Initiate HPCI (Alternate Path - Manual Initiation Pushbutton F,ailsTo Operate)

(2007 NRC / PLOR-300CA) - SET 1

c. 239001 A4.01 - Main Steam System / Open Main Steam Isolation Valves After a Group-1 Isolation (PLOR-083C) - SET 2
d. 209001 A4.04 - Core Spray System I Perform Pump Capacity Test For A, L, M, S 4 IST (Alternate Path - Minimum Flow Valve Fails To Open) - SET 3
e. 223002 A4.03 - Primary Containment Isolation System / Perform a D, EN, S 5 Group I PClS Isolation Reset (GP-8A) (PLOR-024C) - SET 1
f. 262001 A4.04 - AC Distribution / Excite The Main Generator D, s 6 (PLOR-031C) - SET 4
g. 212000 A4.14 - Reactor Protection System / Reset a Full Scram D, EN, L, S 7 (PLOR-004C) - SET 2
h. 400000 A4.01 - Component Cooling Water I Verify Proper Isolation of D,p, s 8 Reactor Building Closed Cooling Water (RBCCW) (20135 NRC) - SET 3
i. 295037 G2.4.35 - Control Rod Drive Hydraulic Systerri / Isolate And Vent D, E, L, R 1 The Scram Air Header - Unit 3 (PLOR-074P)
j. 217000 A2.04 - Reactor Core Isolation Cooling / Defeat Auto Open Signal E, N, R 2 of RClC Torus Suction Valves - Unit 2 (NEW - A 0 13.:3-2)
k. 295028 EA1.03 - Drywell Chilled Water Low Level (Alternate Path - A, E, N, R 5 Manual Makeup to Drywell Chilled Water System) - Unit 2 (NEW - ARC
  • Type Codes Criteria for RO I SRO-I I SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank -

<9 I58 I 5 4 (E)mergency or abnormal in-plant -

> I I > 1/>1 (EN)gineered safety feature - I - I 2 1 (control room system)

(L)ow-Power I Shutdown -

> I 1 1 1 121 (N)ew or (M)odified from bank including 1(A) -

22 I > 2 I 21 (P)revious 2 exams < 3 I 5 3 I 5 2 (randomly selected)

-

(WA > I I >I

- 121 I (S)imuiator 1 1 1 1 ES-301, Page 23 of 27

ES-301 Control Room/ln-Plant Iivstems Outline Form ES-301-2

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Facility: Peach Bottom Date of Examination: 12/08/2008 Exam Level: RO 0 SRO-I SRO-U 0 Operating Test Number: 2008 NRC Control Room Systems@(8 for RO); (7 for SRO-I); (2 or :3 for SRO-U, including 1 ESF)

I/ System / JPM Title 1 I Safety Function

~

a. 202001 A4.01 - Recirculation System / Start a Recirc IPump (Alternate A, D, S 1 Path - Scoop Tube Lockup) (PLOR-309CA) - SET 4
b. 295031 EA1.02 - High Pressure Coolant Injection / Manually Initiate A, D, EN, 2 HPCl (Alternate Path - Manual Initiation Pushbutton F,ailsTo Operate) L, P, s (2007 NRC / PLOR-300CA) - SET 1 ____.
c. 239001 A4.01 - Main Steam System / Open Main Steam Isolation Valves D, L, S 3 After a Group-I Isolation (PLOR-083C) - SET 2
d. 209001 A4.04 - Core Spray System / Perform Pump Capacity Test For A, L, M, S 4 IST (Alternate Path - Minimum Flow Valve Fails To Open) - SET 3
e. 223002 A4.03 - Primary Containment Isolation Systern I Perform a D, EN, S 5 Group I PClS Isolation Reset (GP-8A) (PLOR-024C) - SET 1 f.
g. 212000 A4.14 - Reactor Protection System / Reset a Full Scram D, EN, L, S (PLOR-004C) - SET 2
h. 400000 A4.01 - Component Cooling Water / Verify Proper Isolation of Reactor Building Closed Cooling Water (RBCCW)

In-Plant Systems@(3 for RO); (3 for SRO-I); (3 or 2 for SIRO-U)

  • Type Codes Criteria for RO I SRO-I I SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank -

< 9 1 5 8 I54 (E)mergency or abnormal in-plant -

> I I > 1 1 21 (EN)gineered safety feature - I - I 2 1 (control room system)

(L)ow-Power I Shutdown -

>I 1>1121 (N)ew or (M)odified from bank including 1(A) -

> 2 I > 2 I 21 (P)revious 2 exams < 3 I 5 3 I 5 2 (randomly selected)

-

(WCA > I I> I 1 2 1

-

(S)imulator I

ES-301 Control Roomlln-Plant Svstems Outline Form ES-301-2 Facility: Peach Bottom Date of Examination: 12/08/2008 Exam Level: RO 0 SRO-I 0 SRO-U [XI Operating Test Number: 2008 NRC II/ Control Room Systems@(8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System / JPM Title Type 'Ode* Function I b. I I I I  !

d. 209001 A4.04 - Core Spray System / Perform Pump Capacity Test For A, L, M, S 4 1 Open) - SET 3 1 1s 1;
f. I
g. 212000 A4.14 - Reactor Protection System I Reset a Full Scram D, EN, L, S 7 (PLOR-004C) - SET 2  !
h. 400000 A4.01 - Component Cooling Water / Verity Proper Isolation of D, P, S 8 I!

Reactor Building Closed Cooling Water (RBCCW) (2005 NRC) - SET 3 1 In-Plant Systems@(3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

-I!

j. 217000 A2.04 - Reactor Core Isolation Cooling / Defeat Auto Open Signal of RClC Torus Suction Valves - Unit 2 (NEW - AC) 13.3-2
k. 295028 EA1.03 - Drywell Chilled Water Low Level (Alternate Path - A, E, N, R Manual Makeup to Drywell Chilled Water System) - Unit 2 (NEW - ARC 217 H-5)

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may

  • Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank -< 9 1 5 8 I 5 4 (E)mergency or abnormal in-plant ->I I ? 11 , I (EN)gineered safety feature - I - I 2 1 (control room system)

(L)ow-Power IShutdown ->I1 2 1 1 2 1 (N)ew or (M)odified from bank including 1(A) -> 2 1 2 2 1 ' 1 (P)revious 2 exams -< 3 I 5 3 I 5 2 (randomly selected)

(WCA ->I 1'1 121 (S)imulator ES-30 E g e 23 of 27 I/~

Scenario Outline ES-8-1 1

It Simulation Facility Peach Bottom Scenario No. # I (altered bank) Op Test No. 2008 NRC; 1 Examiners Operators CRS (:SRO)

URO 4TC)

PRO (30P)

Scenario The scenario begins with a plant startup in progress at approximately 5% power following a refueling Summary outage. During shift turnover, the crew is directed to swap CRD pumps due to a noisy bearing on the A pump. Following the CRD pump swap, the B drywell chiller trips, requiring the crew to place the standby drywell chiller in service in accordlance with ON-I20 High Drywell Temperature.

Next, a loss of MCC E224-R-B results in a loss of the B RPS MG set, a half scram and PClS outboard Group II isolation. The crew will investigate, transfer RPS to the alternate supply and reset the half scram and PClS isolation. Following the Tech Spec evaluation, startup level controller LCV-8091 will fail open, requiring the crew to rrianually restore and control RPV water level in accordance with OT-I 10 Reactor High Level. This event is further complicated by an inadvertent RClC initiation, requiring entry into OT-104 Positive Reactivity Insertion and manual shutdown of RCIC.

Following this, an EHC failure will cause reactor pressure to rise, requiring entry into OT-102 Reactor High Pressure. The crew will be?unable to reduce reactor pressure. The reactor will fail to automatically scram on high pressure and the crew will be required to insert a manual scram. Shortly after the scram, a leak will develop in the t.orus, requiring the crew to enter T-103 Secondary Containment Control and T-I 02 Primary Containment Control. A turbine bypass valve (#I) will fail (remain) open and, due to a failure of the inode switch, will result in MSlVs closing when reactor pressure decreases below 850 psig. As torus level continues to drop, the crew will be required to perform T-I 12 Emergency Blowdown.

Event Malfunction Event Event No. No. Type* Description 1 N URO SwapCRDpumps CRS C PRO Drywell chiller trip CRS C URO Loss of MCC E224-R-B resulting in half scram and Group II outboard TS PRO isolation I transfer RPS power supplies, reset half scram and isolations CRS 4 1 I URO Startup level controller (LCV-8091) failure

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CRS I PRO Inadvertent RClC initiation TS CRS 6 C URO EHC failure causes rising reactor pressure / reactor scram with mode CRS switch failurle (manual scram works) 7 M ALL Torus leak iiito secondary containment (torus room) leading to emergency blowdown / turbine bypass valve fails open, causing MSlVs to close (due to failed mode switch)

Scenario Outline ES-R3-1 1

I, Simulation Facility Peach Bottom Scenario No. #2 (altered bank) Op Test No. 2008 NR( :

1 Examiners Operators CRS (3RO)

URO I ATC)

PRO (30P)

Scenario The scenario begins with the reactor at approximately 76% power with power ascension on hold.

Summary The crew will perform ST-0-001-200-2 Turbine Stop Valve Closure and EOC-RPT Functional Test when an RPS failure will require the crew to make a Tech Spec declaration. This will be followed by a trip of the in-service TBCCW pump with a failure of the standby pump to auto-start. The crevt will be required to respond IAW ON-118 Loss of TBCCW and place the standby TBCCW pump in service. Following this, the ASRV will inadvertently open, requiring the crew to take actions IAW OT-I14 Inadvertent Opening of a Relief Valve. Power will be reduced in accordance with GP-9-2 Fast Power Reduction. The crew will be successful in closing the ASRV by directing plant operators to pull fuses for the valve.

A small steam leak inside the primary containment will occur next. The crew will be required to take actions in accordance with OT-101 High Drywell Pressure. When the reactor is scrammed, a hydraulic ATWS will occur, requiring the cirew to enter T-101 RPV Control and T-I 17 LeveVPower Control. A failure of the Standby Liquid Control pump will require the crew to start the other pump in order to successfully lower reactor power.

The crew will also be required to enter T-102 Primary Containment Control due to high drywell pressure. After diagnosing the inability to spray the containment due to an instrument failure, the crew will perform T-I12 Emergency Blowdown. One ADS SRV will fail to open, requiring the opening of another SRV. The crew will need to implement T-216 Control Rod Insertion By Manual Scram Or Individual Scram Test Switches and T-220 Driving Control Rods During Failure To Scram to terminate the ATWS.

Initial IC-72, 76% power Conditions Turnover See Attached Shift Turnover Sheet Event Event Description main turbine stop valve functional test / RPS failure during

~~~ ~

2 C URO TBCCW pump trip w/ failure of standby pump to auto-start CRS C PRO SRV inadvertently opens, requiring torus cooling to be maximized /

TS CRS SRV closes when control power fuses are removed 4 R URO Fast power reduction due to SRV opening CRS

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5 M ALL Steam leak in the primary containment / hydraulic ATWS / pressrrre instrument f<ailureprevents using containment sprays 6 C URO Standby liquid control pump trips requiring manual start of the CRS alternate pump 7 I PRO ADS SRV fails to open during emergency blowdown requiring an CRS additional SlRV to be opened

Scenario Outline ES-13-1 Simulation Facility Peach Bottom Scenario Nlo. #3 (modified bank) Op Test No. 2008 NR(

Examiners Operators CRS ( SRO)

URO ATC)

PRO I BOP)

Scenario The scenario begins with the reactor at 95% power. Immediately after shift turnover the crew will Summary commence the HPCl functional and in-service test. While the test is in progress, the running Service Water pump will trip on overcurrent, requiiring the crew to place the standby pump in service using the system operating procedure. The crew will then receive a report from the field of a HPCl system cooling water leak, requiring HPCl to be shutdown and declared inoperable. Next, a loss of DC:

power to an in-service RPS MG set output breaker will occur, requiring application of the appropriate Tech Spec. When this is complete, the A, Condensate pump will trip without the expected Recirc System runback. Power must be manually reduced using recirc flow to prevent a low-level scram.

When conditions have stabilized, #2 Auxiliary Bus will trip on overcurrent, removing the remaicing Condensate pumps from service. An RPS failure will prevent the automatic and manual scrams, requiring entry into T-101 RPV Control, T-117 LeveVPower Control, and the use of Alternate Rod Insertion (ARI) to shutdown the reactor. The scram discharge volume will fail to completely isolate and must be manually isolated. RClC will trip when either started manually or automatically, which will remove the final source of high pressure feed. As level deteriorates, the crew should start available low pressure ECCS pumps and when the crew determines level cannot be restored and maintained above -195 inches, the reactoir will be depressurized in accordance with T-I 12 Emergency Blowdown, after terminating and preventing injection per T-240 (due to the six-rod ATWS). Low pressure ECCS will be available to recover reactor level.

Event Malfunction Event Event No. No. Type* Description -

1 N PRO Perform HFCI surveillance testing CRS 2 C URO Service Water pump trip, requiring manual start of standby pump CRS 3 C PRO HPCl cooling water leak requires HPCl shutdown TS CRS 4 TS CRS Loss of DC power to RPS MG set output breaker 5 R URO Condensate pump trip with recirc runback failure / power reduction CRS 7

I C ALL URO

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Loss of #2 auxiliary bus / loss of condensate & feedwater / RClC trips on over-speed during startup and cannot be reset RPS failure requires ARI initiation to scram the reactor / ATWS (six CRS control rods) requires terminating and preventing injection before emergency depressurization

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8 I PRO Two in-series scram discharge volume (SDV) vent valves fail to CRS automatically isolate I I I

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS) Tech Spec

Scenario Outline ES-11-1 Simulation Facility Peach Bottom Scenario No. #4 (altered bank) Op Test No. 2008 NRC:

Examiners Operators CRS (3RO)

URO ATC) 1 PRO I BOP)

SPARE Scenario Scenario The scenario begins with the reactor at 82% power and a plant shutdown in progress. The crew will Summary lower reactor power using reactor recirculation flow and once below 80% power, the crew will secure a condensate pump. Following the condensate pump shutdown, the 2SU-E feeder will trip. Tt-e E12 bus will not fast transfer to the other startup feed, causing the E-I diesel to start and its breaker to automatically close onto the bus Automatic cooling to the diesel will not occur, requiring the crew to establish cooling manually. The crew will be required to make a Tech Spec declaration for the electrical failure.

This will be followed by a trip of the B rec:irc pump due to a failed RPT breaker. The crew should carry out the actions of OT-I 12 Unexplained/UnexpectedChange in Core Flow, which includes establishing single loop operation and corisulting Technical Specifications. A loss of offsite power will occur next, requiring entry into SE-11 Lo!ss of Off-Site Power. The crew should stabilize plant parameters using T-100 Scram and should recognize and respond to a failure of the HPCl flow controller to operate in automatic. The E-4 diesel generator will fail to automatically start, and the E-3 diesel generator will not start at all. The crew will be required to manually start the E-4 diesel generator using the quick-start pushbutton in order to spray the Drywell later in the scenario.

Following this event, a steam leak will develop in the drywell, requiring the crew to take actions in accordance with OT-101 High Drywell Pressure, and execute T-101 RPV Control and T-10%

Primary Containment Control. The high drywell pressure condition will prevent HPCl from being used to control reactor pressure, resulting in further challenge to the primary containment.

Event Malfunction Event Event No. No. Type* Description 1 R URO Lower reactor power with reactor recirculation flow CRS 2 N PRO Secure a condensate pump CRS I3l Loss of 2SlU-E startup feed with failure of the E12 bus to fast transfer /

E l EDG auto starts with failure of ESW cooling to diesel auxiliaries 1I I TS C URO CRS Recirc RPI- breaker trip / single loop operation I I I M ALL I Loss of off-site power / steam leak in the drywell I PRO CRS I E-4 diesel !generatorfails to auto start 7 I URO HPCl flow (controllerfails in automatic CRS

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